JPH04256892A - Fuel for light water reactor - Google Patents
Fuel for light water reactorInfo
- Publication number
- JPH04256892A JPH04256892A JP3037841A JP3784191A JPH04256892A JP H04256892 A JPH04256892 A JP H04256892A JP 3037841 A JP3037841 A JP 3037841A JP 3784191 A JP3784191 A JP 3784191A JP H04256892 A JPH04256892 A JP H04256892A
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- uranium
- light water
- pellets
- water reactor
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 239000000446 fuel Substances 0.000 title claims abstract description 52
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims description 12
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims abstract description 24
- 229910052770 Uranium Inorganic materials 0.000 claims abstract description 23
- 239000008188 pellet Substances 0.000 claims abstract description 21
- JFALSRSLKYAFGM-OIOBTWANSA-N uranium-235 Chemical compound [235U] JFALSRSLKYAFGM-OIOBTWANSA-N 0.000 claims abstract description 9
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 claims abstract description 7
- 229910000439 uranium oxide Inorganic materials 0.000 claims abstract description 7
- 230000000694 effects Effects 0.000 abstract description 9
- 238000005253 cladding Methods 0.000 abstract description 5
- 239000003758 nuclear fuel Substances 0.000 description 6
- 230000007423 decrease Effects 0.000 description 3
- 229910001093 Zr alloy Inorganic materials 0.000 description 2
- 239000011248 coating agent Substances 0.000 description 2
- 238000000576 coating method Methods 0.000 description 2
- 238000002485 combustion reaction Methods 0.000 description 2
- 239000000498 cooling water Substances 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000005245 sintering Methods 0.000 description 2
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 230000020169 heat generation Effects 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000002156 mixing Methods 0.000 description 1
- -1 natural uranium Chemical compound 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
本発明は原子燃料の改良に関する。更に詳述すると、本
発明は軽水炉型原子炉用燃料に関するものである。TECHNICAL FIELD This invention relates to improvements in nuclear fuel. More specifically, the present invention relates to a fuel for a light water reactor type nuclear reactor.
【0001】0001
【従来の技術】従来、軽水炉用燃料は濃縮ウランのペレ
ットを被覆管で覆った棒状物としている。例えば、現状
の軽水炉は、もっぱらジルカロイの被覆管に燃料の濃縮
ウラン・UO2 のペレットを充填した燃料棒を束ねた
燃料集合体を使用している。燃料棒は、図2に示すよう
に、乾燥したUO2 ペレット101をジルカロイ管1
02にヘリウムと共に充填し、溶接して閉じられている
。
UO2 は、焼いた濃縮ウラン・UO2 を一旦粉末に
したものを混ぜ合せてペレット状に固め、それを高密度
に焼結して精度の高いペレットとしている。BACKGROUND OF THE INVENTION Conventionally, fuel for light water reactors is a rod-shaped product made of enriched uranium pellets covered with a cladding tube. For example, current light water reactors exclusively use fuel assemblies in which fuel rods filled with enriched uranium/UO2 pellets are bundled into Zircaloy cladding tubes. As shown in FIG. 2, the fuel rod is made by passing dried UO2 pellets 101 into a Zircaloy tube 1.
02 is filled with helium and welded closed. UO2 is made by mixing baked enriched uranium (UO2) into powder, solidifying it into pellets, and then sintering it to a high density to make highly accurate pellets.
【0002】0002
【発明が解決しようとする課題】しかしながら、この従
来の燃料では、燃料の高燃焼度化に伴って、燃料の中心
温度が上昇して行く問題を有する。この燃料は高燃焼時
に、燃料ペレットの中心部より燃料ペレットの表面の方
がより燃焼する現象(リム効果)が起こる。一方、燃料
は燃焼に伴い熱伝導度が低下する性質がある。したがっ
て、通常は燃料棒で発生する熱は燃料ペレット表面を通
過し、燃料棒周囲の冷却水に伝達されるが、リム効果に
よる燃料ペレット表面での熱伝導の低下が起こると冷却
水への熱の伝導を阻害し、燃料中心温度を上昇させると
考えられる。燃料の中心温度が余り高くなると燃料棒の
破損する危険性が増すため、燃料の中心温度の上昇は制
限しなければならない。このため、燃料の中心温度の上
昇を制限するため燃料の高燃焼度化が制限される因子の
1つともなっている。However, this conventional fuel has a problem in that as the burnup of the fuel increases, the central temperature of the fuel increases. When this fuel burns at a high rate, a phenomenon occurs in which the surface of the fuel pellet burns more than the center of the fuel pellet (rim effect). On the other hand, fuel has a property that its thermal conductivity decreases as it burns. Therefore, normally the heat generated in the fuel rods passes through the fuel pellet surface and is transferred to the cooling water around the fuel rods, but if heat conduction at the fuel pellet surface decreases due to the rim effect, heat is transferred to the cooling water. It is thought that this inhibits the conduction of fuel and increases the core temperature of the fuel. If the core temperature of the fuel becomes too high, the risk of damage to the fuel rods increases, so the increase in the core temperature of the fuel must be limited. For this reason, this is one of the factors that limits the increase in burnup of the fuel in order to limit the rise in the center temperature of the fuel.
【0003】本発明は、リム効果を低減する軽水炉用燃
料を提供することを目的とする。SUMMARY OF THE INVENTION An object of the present invention is to provide a fuel for a light water reactor that reduces the rim effect.
【0004】0004
【課題を解決するための手段】かかる目的を達成するた
め、本発明の軽水炉用燃料は、燃料ペレットの外表面に
天然ウラン等のウラン235( 235U)の割合の少
ない酸化ウランを被覆している。[Means for Solving the Problems] In order to achieve the above object, the light water reactor fuel of the present invention coats the outer surface of the fuel pellet with uranium oxide containing a small proportion of uranium-235 (235U) such as natural uranium. .
【0005】[0005]
【作用】したがって、燃料表面付近では燃料が少なくな
ることから、燃料表面の燃焼が燃料ペレット中心より進
まず、リム効果が低減される。このため、熱伝導度の低
下を防いで燃料中心の温度上昇を制限する。[Operation] Therefore, since there is less fuel near the fuel surface, combustion on the fuel surface does not progress beyond the center of the fuel pellet, and the rim effect is reduced. This prevents a decrease in thermal conductivity and limits the temperature rise at the center of the fuel.
【0006】[0006]
【実施例】以下、本発明の構成を図面に示す実施例に基
づいて詳細に説明する。DESCRIPTION OF THE PREFERRED EMBODIMENTS Hereinafter, the structure of the present invention will be explained in detail based on embodiments shown in the drawings.
【0007】図1に本発明の軽水炉用燃料の実施例を示
す。この燃料は、濃縮ウランから成る燃料ペレット1の
表面にウラン235 の割合の少ない酸化ウラン2を被
覆してから被覆管3内に充填されている。ウラン235
の割合の少ない酸化ウラン(以下被覆ウランとも略称
する)2としては例えば天然ウランの使用が好ましい。FIG. 1 shows an embodiment of the light water reactor fuel of the present invention. This fuel is filled into a cladding tube 3 after the surface of a fuel pellet 1 made of enriched uranium is coated with uranium oxide 2 having a low proportion of uranium 235. uranium 235
As the uranium oxide (hereinafter also referred to as coated uranium) 2 having a small proportion of uranium, it is preferable to use, for example, natural uranium.
【0008】被覆ウラン2は濃縮ウラン1のペレット製
造過程において被覆される。例えば濃縮ウラン1をペレ
ット状に固めた後にその表面に被覆ウラン2を被覆し、
一緒に高密度に焼結するか、あるいはペレット1を焼結
した後に被覆される。The coated uranium 2 is coated during the process of producing enriched uranium 1 pellets. For example, after solidifying enriched uranium 1 into a pellet, its surface is coated with coated uranium 2,
Either sintered together to a high density or coated after sintering the pellets 1.
【0009】この被覆ウラン2の厚み及び量は、例えば
200μm〜300μm程度が好ましい。これ以上多い
と燃料ペレット1での発熱割合が高くなり過ぎ、少な過
ぎるとリム効果を抑制することができない。The thickness and amount of this coated uranium 2 is preferably about 200 μm to 300 μm, for example. If the amount is more than this, the heat generation rate in the fuel pellets 1 will become too high, and if it is too small, the rim effect cannot be suppressed.
【0010】斯様に、燃料ペレット1の外表面に原子燃
料物質であるウラン235 の割合が濃縮ウランより少
ない天然ウラン2等を被覆すると、燃料表面付近に燃料
が少ないことになる。このため、燃料表面の燃焼が燃料
中心より進まず、リム効果が低減される。したがって、
従来の燃料より高燃焼度時の燃料中心温度が低減され、
燃料棒の安全性が向上する。依って、より高燃焼度まで
燃料の使用が可能となり、高燃焼度化によって達成され
る発電コストの低減が促進され、経済性の向上にもつな
がる。[0010] In this way, when the outer surface of the fuel pellet 1 is coated with natural uranium 2 or the like, which has a lower proportion of uranium 235, which is a nuclear fuel material, than enriched uranium, there will be less fuel near the fuel surface. Therefore, combustion on the fuel surface does not progress beyond the center of the fuel, reducing the rim effect. therefore,
The fuel center temperature at high burnup is lower than that of conventional fuels,
Improves fuel rod safety. Therefore, it becomes possible to use fuel up to a higher burnup, and the reduction in power generation costs achieved by increasing the burnup is promoted, leading to improved economic efficiency.
【0011】[0011]
【発明の効果】以上の説明より明らかなように、本発明
の軽水炉用燃料は、燃料ペレットの外表面に天然ウラン
等のウラン235 の割合が濃縮ウランより少ない酸化
ウランを被覆することは燃料外径に変更を与えないこと
から、燃料中心温度以外の原子炉の各種特性に影響を与
えない。このため、原子炉の持つ安全性を向上するのみ
で、原子炉プラントの特性を損なうことなく現行の軽水
炉での利用が容易である。また、燃料の製造においては
、天然ウラン等を被覆する工程を追加するだけで容易に
製造が可能であり、製造費用への影響が少ない経済的で
ある。[Effects of the Invention] As is clear from the above explanation, in the light water reactor fuel of the present invention, coating the outer surface of the fuel pellet with uranium oxide, such as natural uranium, which has a lower proportion of uranium-235 than enriched uranium, is not a fuel-related problem. Since it does not change the diameter, it does not affect various characteristics of the reactor other than the fuel center temperature. Therefore, it can be easily used in current light water reactors without impairing the characteristics of the nuclear reactor plant, simply by improving the safety of the nuclear reactor. Moreover, in the production of fuel, it can be easily produced by simply adding a step of coating natural uranium, etc., and it is economical with little impact on production costs.
【図1】本発明の軽水炉用燃料の一実施例を示す燃料棒
の横断面図である。FIG. 1 is a cross-sectional view of a fuel rod showing an embodiment of the fuel for a light water reactor according to the present invention.
【図2】従来の軽水炉用燃料の一例を示す横断面図であ
る。FIG. 2 is a cross-sectional view showing an example of a conventional light water reactor fuel.
1 濃縮ウラン
2 ウラン235 の割合の少ない酸化ウラン3
被覆管1 Enriched uranium 2 Uranium oxide with a low proportion of uranium-235 3
cladding tube
Claims (1)
のウラン235 の割合の少ない酸化ウランを被覆した
ことを特徴とする軽水炉用燃料。1. A fuel for a light water reactor, characterized in that the outer surface of fuel pellets is coated with uranium oxide containing a low proportion of uranium-235, such as natural uranium.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP3037841A JPH04256892A (en) | 1991-02-08 | 1991-02-08 | Fuel for light water reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP3037841A JPH04256892A (en) | 1991-02-08 | 1991-02-08 | Fuel for light water reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH04256892A true JPH04256892A (en) | 1992-09-11 |
Family
ID=12508761
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP3037841A Pending JPH04256892A (en) | 1991-02-08 | 1991-02-08 | Fuel for light water reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH04256892A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0788117A1 (en) * | 1996-01-30 | 1997-08-06 | Siemens Power Corporation | Nuclear fuel pellet |
US6002735A (en) * | 1996-01-30 | 1999-12-14 | Siemens Power Corporation | Nuclear fuel pellet |
-
1991
- 1991-02-08 JP JP3037841A patent/JPH04256892A/en active Pending
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0788117A1 (en) * | 1996-01-30 | 1997-08-06 | Siemens Power Corporation | Nuclear fuel pellet |
US5991354A (en) * | 1996-01-30 | 1999-11-23 | Siemens Power Corporation | Nuclear fuel pellet |
US6002735A (en) * | 1996-01-30 | 1999-12-14 | Siemens Power Corporation | Nuclear fuel pellet |
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